Projects per year
Overview
Expertise related to UN Sustainable Development Goals
In 2015, UN member states agreed to 17 global Sustainable Development Goals (SDGs) to end poverty, protect the planet and ensure prosperity for all. This person’s work contributes towards the following SDG(s):
Education/Academic qualification
Eng-Aerospace, Bachelor's Degree
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Researcher collaborations from the last five years
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Projects
- 1 Active
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Experimental thermofluidic validation of TCR fuel elements using distributed temperature and flow sensing
Bindra, H. (PI), Kawaji, M. M. (CoPI), Chen, K. K. (CoPI), Jain, P. (CoPI) & See, N. (CoPI)
Nuclear Energy University Program
01/1/21 → …
Project: Research
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Effect of Heat Transfer Coefficient on Time to Onset of Natural Circulation
Eaheart, M. & See, N., 2024, In: Transactions of the American Nuclear Society. 130, 1, p. 1320-1323 4 p.Research output: Contribution to journal › Conference article › peer-review
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Final CRADA Report – NFE-21-08642 Multiphysics Design Optimization and Additive Manufacturing of Nuclear Components (Executive Summary)
See, N., Popov, E. & Pointer, W., Jun 2024Research output: Other contribution › Technical Report
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Fractionation of UF6 and daughter progeny in storage cylinders from external heating
Wilson, B. A., Peplow, D. E., Bledsoe, K. C., See, N. D., Rose, P. B. & Fugate, G. A., 2024, (Accepted/In press) In: Journal of Radioanalytical and Nuclear Chemistry.Research output: Contribution to journal › Article › peer-review
Open Access -
Integrated Process and Materials Modeling for Development of Additive Manufacturing of Refractory Materials for Critical Applications
Panicker, N., Prabhune, B. C., See, N., Delchini, M. O., Jordan, B., Lim, B., Nag, S. & Lee, Y., Feb 2024Research output: Other contribution › Technical Report
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Air Ingress and DLOFC Studies in Scaled HTGR Geometry using Additively Manufactured TCR Fuel Elements
Sieh, B., Bindra, H., Jain, P., Petrie, C. & See, N., 2023, Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. American Nuclear Society, p. 3416-3427 12 p. (Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
Open Access